A5039851110- Fusion materials and technologies
- Nuclear Materials and Properties
- Metal and Thin Film Mechanics
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Microstructure and Mechanical Properties of Steels
- Ion-surface interactions and analysis
- Hydrogen embrittlement and corrosion behaviors in metals
- Fatigue and fracture mechanics
- Particle accelerators and beam dynamics
- Non-Destructive Testing Techniques
- Magnetic confinement fusion research
- Graphite, nuclear technology, radiation studies
- Microstructure and mechanical properties
- Metal Alloys Wear and Properties
- Advanced ceramic materials synthesis
- High-Temperature Coating Behaviors
- High Temperature Alloys and Creep
- Titanium Alloys Microstructure and Properties
- Superconducting Materials and Applications
- Muon and positron interactions and applications
- Nuclear materials and radiation effects
- Advanced materials and composites
- High Entropy Alloys Studies
- Advanced Surface Polishing Techniques
Japan Atomic Energy Agency
2014-2024
Japan Proton Accelerator Research Complex
2018-2024
Advanced Science Research Center
1995-2023
Fermi National Accelerator Laboratory
2019
Osaka University of Pharmaceutical Sciences
2016
Osaka Prefecture University
1993
Osaka University
1991-1992
Tokyo University of Science
1990
Deuterium retention and blistering in the near-surface region of tungsten exposed to high fluences (up 1027 D m−2) flux (1022D+ m−2 s−1) low energy (38 eV) deuterium plasma were examined with scanning electron microscopy, focused ion beam thermal desorption spectroscopy (TDS). Two kinds blisters appeared at recrystallized 520 K. One is large sizes a few tens micrometres varying ratios height against width 0.6), other small less than ratio diameter (about 0.7). A peculiar phenomenon blister...
IFMIF, the International Fusion Materials Irradiation Facility, is presently in its engineering validation and design activities (EVEDA) phase under Broader Approach Agreement.
The International Fusion Materials Irradiation Facility (IFMIF), presently in its Engineering Validation and Design Activities (EVEDA) phase under the frame of Broader Approach Agreement between Europe Japan, accomplished summer 2013, on schedule, EDA with release engineering design report IFMIF plant, which is here described. Many improvements from former phases are implemented, particularly a reduction beam losses operational costs thanks to superconducting accelerator concept, re-location...
The Engineering Validation and Design Activities (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF), an international collaboration under Broader Approach Agreement between Japan Government EURATOM, aims at allowing a rapid construction phase of IFMIF in due time with understanding cost involved. three main facilities (1) Accelerator Facility, (2) Target (3) Test are subject validation activities that include either full scale prototypes or smartly devised scaled...
Four kinds of tungsten samples were exposed to 76 eV D2+ ions (38 D−1) at a flux 1022 D m−2s−1. For plasma exposure 315 K, blistering occurred more significantly on the unrecrystallized and single crystal W than partially fully recrystallized samples. The un-recrystallized sample showed largest retention ratio same fluence. higher fluences (up 1027 m−2), phenomena bursting release deuterium blister clearly observed. Preliminary positron annihilation measurements indicated that vacancy...
The necessity of a neutron source for fusion materials research was identified already in the 70s. Though neutrons induced degradation present similarities on mechanistic approach, thresholds energies crucial transmutations are typically above fission spectrum. generation He via 56Fe (n,α) 53Cr future reactors with around 12 appm/dpa will lead to swelling and structural embrittlement. Existing sources, namely or spallation sources different degradation, attempts extrapolation unsuccessful...
The microstructures and mechanical properties of bcc iron-based high entropy alloy (HEA) Fe-20Mn-15Cr-10 V-10Al-2.5C (in at.%) without Co Ni elements have been investigated for applications in fields such as nuclear reactors magnetic motors aircraft automobiles. This was normalized at 1150 °C 2 h then water quenched, it heated 800 10 min quenched. had body center cubic (BCC)-phase vanadium carbides with 2–3 μm arranging along grain boundaries, the Vickers hardness 520 Hv, harder than pure...
The engineering validation and design activity (EVEDA) for the International Fusion Materials Irradiation Facility (IFMIF) is proceeding as one of ITER broader approach activities. In concept IFMIF, two 40 MeV deuteron beams are injected into a liquid Li stream (Li target) flowing at velocity 15 m s −1 . EVEDA test loop (ELTL) aimed validating hydraulic stability target up to 20 under vacuum condition 10 −3 Pa most important issue. Construction ELTL, which largest metal possessing 5.0 3...